IR 05000454/2006007

IR 05000454-06-007(DRS) and IR 05000455-06-007(DRS); 01/30/06-02/02/06; Exelon Nuclear Corporate, Mid-West Rog Headquarters; 08/14/06-08/18/06; Byron, Units 1 & 2. Security Review of Security Training and Fitness-for-Duty; Event Follow-up;

ML062540414
Person / Time
Site:	Byron
Issue date:	09/08/2006
From:	Kenneth Riemer Plant Support Branch II
To:	Crane C Exelon Generation Co, Exelon Nuclear
References
IR-06-007 IR-06-007
Download: ML062540414 (7)

Text

September 8, 2006Mr. Christopher M. CranePresident and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555SUBJECT:BYRON STATION, UNITS 1 AND 2NRC PHYSICAL SECURITY BASELINE INSPECTION REPORTNO. 05000454/2006007(DRS); 05000455/2006007(DRS)

Dear Mr. Crane:

On August 18, 2006, the U.S. Nuclear Regulatory Commission (NRC) completed a baselinesecurity inspection of your Byron Station and Exelon Nuclear Corporate. The enclosed report documents the results of this inspection, which were discussed on February 2, 2006, with Mr. D. Evans, on August 18, 2006, with Ms. Snow, and on August 30, 2006, with Mr. D. Hoots and other members of your staff.This inspection examined activities conducted under your license as they relate to public healthand safety, the common defense and security, and to compliance with the Commission's rules and regulations, orders, and with the conditions of your license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel.EXEMPT FROM PUBLIC DISCLOSUREMay be exempt from public release under the Freedom ofInformation Act (5 U.S.C. 552)Exemption number: 5 Nuclear Regulatory Commission review required before publicrelease.K.Brooks, RIII/DRS/PSB Name and organization of person making determination.

Date of determination: 08/22/06 Enclosure Contains . Upon separation, this page is Decontrolled. C. Crane-2-This report documents three findings of very low security significance (i.e., Green as determinedby the Physical Protection Significance Determination Process). The deficiencies were promptly corrected or compensated for, and the plant was in compliance with applicable physical protection and security requirements within the scope of this inspection before the inspector left the site.Nuclear Regulatory Commission is treating these violations as Non-Cited Violations (NCVs)consistent with Section VI.A.1of the NRC Enforcement Policy because of the very low security significance of these violations, and because they are entered into your corrective action program. If you contest this Non-Cited Violation, you should provide a response within 30 days of the date fo this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator Region III, the Director, Office of Enforcement, U.S. Nuclear RegulatoryCommission, Washington, DC 20555-0001; and the NRC Resident Inspector at the ByronStation.The findings were both NRC-identified and Licensee-identified. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will beavailable electronically for public inspection in the NRC Public Document Room, or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS), accessiblefrom the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public ElectronicReading Room). However, because of the security-related information contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letter's enclosure will not beavailable for public inspection.In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for yourresponse, if any. This practice will ensure that your response will not be made availableelectronically for public inspection in the NRC Public document room or from the NRC's document system, ADAMS. If Safeguards Information is necessary to provide an acceptableresponse, please provide the level of protection described in 10 CFR 73.21. Otherwise, markyour entire response "Security-Related Information-Withhold Under 10 CFR 2.390" and follow the instructions for withholding in 10 CFR 2.390Enclosure Contains . Upon separation, this page is Decontrolled. C. Crane-3-Should you have any questions concerning this inspection, we will be pleased to discuss themwith you.

Sincerely,

/RA/Kenneth Riemer, ChiefPlant Support Branch Division of Reactor SafetyDocket Nos. 50-454; 50-455License Nos. NPF-37; NPF-66Enclosure: Inspection Report 05000454/2006007(DRS);05000455/2006007(DRS)w/Attachment: Supplemental Information ( )cc w/encl ( )

B. Westriech, NSIR/DNS Licensing Assistant, NSIR/DNS/RSS D. Combs, Byron Site Security Manager State Liaison OfficerEnclosure Contains . Upon separation, this page is Decontrolled.